ML17332A286
| ML17332A286 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/31/1994 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1134A, NUDOCS 9409090022 | |
| Download: ML17332A286 (40) | |
Text
P R.I@3 H.IMW 1
h,CCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9409090022 DOC.DATE: 94/08/31 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION P
FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T.
Document Control Branch (Document Control Desk)
R
SUBJECT:
Forwards Donald C Cook Nuclear Plant Simulation Facility Four Year Rept.
DISTRIBUTION CODE: A005D COPIES RECEIVED:LTR t
ENCL
(
SIZE:
TITLE: Simulator Facility Certification GL-90-08 NOTES:
0 RECIPIENT ID CODE/NAME HICKMAN,J INTERNAL.~CENTRAL FILE 0 i
EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 RECIPIENT ID CODE/NAME NRR/DRCH/HOLB COPIES LTTR ENCL 1
1 D
0 C
N NOTE TO ALL"RIDS'ECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE!CONTACTTI.IE DOCUMENTCOi iTROL DESK, ROOM P!-37 (EXT. 504-2083 ) TO ELIMfiNATEYOUR NAMEFROM DISTRIBUTIONLIS'rs r'OR DOCUMEi4TS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 4
ENCL 4
Indiana Michigan Power Company P.O. Box 16631 s,
Columbus, OH 43216 AEP:NRC'1134A Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
COOK NUCLEAR PLANT SIMULATION FACILITY FOUR YEAR REPORT U.
S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Attn:
W. T. Russell August 31, 1994
Dear Mr. Russell:
In 'accordance with 10CFR55.45, (b)(5)(ii), Indiana Michigan Power Company hereby submits the Cook Nuclear Plant Simulation Facility four year report.
The attached report encompasses both Cook Nuclear Plant Unit 1
(50-315) and Cook Nuclear Plant Unit 2
(50-316).
Additionally, although not required by 10CFR55.45, included for your convenience is Form NRC-474 for both units.
Sincerely, E.
E. Fitzpatrick Vice President Attachment ar cc:
A. A. Blind Frank Collins - NRR/LPEB G. Charnoff J.
B. Martin - Region II NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett ml~ Il A q409090022
~408>~
'ADOCK 05000315 PDR
ATTACHMENT TO AEP:NRC:113'ONALD C.
COOK NUCLEAR PLANT SIMULATION PACXLITY POUR YEAR REPORT
NR(r FOAM4?4 (td4tf REOULA 8
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COOK NUCLEAR,PLANT 50- 315 INDIANA.MICHIGAN POWER COKPANY 8/24/94 Thfa ts lo oerttry thou
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s thoro aro ~y sttos pltoHS tolho oerttgoagon of thto Item, cHttctt HsfLE l 1 anrf rtsscoa Mfyen 1&colonel pages aa noosssary.
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COOK NUCLEAR PLANT TRAINING CENTER ONE COOK PLACE BRIDGMAhit MI 49106 glMLfLATloHFActUTYPEftpofgtAHGETEETABsfftAcfsATTAcHBD. (forfrorfortnertrNtests osddrotsdtn tfropsrfrrd sndfrr(ftsftn gro crete ofsrftoertt~
oEDctt~H oF PEftfottMANOETc+TlNcottpLEAzpe ffttaort NI4rrrrrnrdpagw at sosssssyondrdtntrry pro patt srrfpormborrrffoosrcrouot f No performance testing was performed specific to the Unit One "Training Load" during the last four year period.
Performance testing of the simulator was performed in accordance with,the testing schedule per the'riginal certification submittal on Unit Two "Training.Load".
Refer to the Cook Nuclear Plant Simulator Four Year Report Unit Two for performance testing abstract and completion dates.
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No performance testing will be performed specific to a Unit One "Training Load".
Refer to the Cook Nuclear Plant Simulator Foui Year, Report Unit Two pages 26 thru 34 for the schedule of certification testing to be performed.over the next four year period on the Unit Two'Training Load".
Approximately 25% of all malfunction testing is schedule annually.
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Attachment to AEP:NRC:1134A Page 2
DONALD C.
COOK NUCLEAR PLANT SIMULATOR FOUR YEAR REPORT UNIT ONE A.
Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 55 Subpart E, Section 55.45.
To comply with 10 CFR 55.45, a report to the Commission which identifies simulator testing status must be submitted by the fourth anniversary of original certification. The purpose of this report is to satisfy this reporting requirement for-Cook Nuclear Plant simulator.
This report addresses the use of Cook Nuclear Plant simulator for training on Cook Nuclear Plant Unit 1.
B.
References Title 10, Code of Federal regulations, Part 55,
'Operator Licenses',
Subpart E, Section 45.
2.
U.
S. Nuclear Regulatory Guide 1.149
'Nuclear Power Plant Simulation Facilities for use in Operator License Examinations.
3.
- 1985,
'Nuclear Power Plant Simulators for use in Operator Training.
C.
Reporting Requirements The requirements of this report as outlined in 10 CFR 55 are:
Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any.
Subpart E, Section 55,45 (b)(5)(ii).
2.
A description of performance testing completed for the simulation facility.
Subpart E, Section 55.45 (b) (5) (vi).
Attachment to AEP:NRC:1134A Page 3
3.
A description of the performance tests, if different, to be conducted on the simulation facility during the subsequent four year period.
Subpart E, Section 55.45 (b)(5)(vi).
4.
A schedule for.the conduct of approximately 25 percent of the performance tests per year for the subsequent four-years.
Subpart E, Section 55.45 (b)(5)(vi).
D.
Discussion The Cook Nuclear Plant simulator functions to provide training for both Units of the Cook Nuclear Plant. Unit 2 four-year report is also provided herein.
The simulator is modelled to Cook Nuclear Plant Unit 2.
The initial certification report provided a demonstration that the differences between the units were not so significant that they impacted the ability of the simulation facility to meet the requirements and guidance of ANSI/ANS-3.5 1985 per NRC Regulatory Guide 1.149 'he simulator was certified as acceptable for training on both units based upon this study and a
commitment made to maintain a Unit 1 'raining load' The Unit 1 'raining load',
although developed, has not been used for training during the course of the four-year period from initial certification to present.
Training commitments for simulator
- usage, simulator equipment limitations, and simulator staffing limitations preclude maintaining a Unit 1 "training load". Based upon the following rationale, Cook'uclear Plant proposes to no longer maintain a Unit 1
" training load".
An evaluation was performed on the Unit 1 specific plant modifications installed in Unit 1 from January 1,
- 1990, to
- present, to determine the impact of those changes upon the original certification differences study.
This evaluation determined that as a result of a change to Unit 1 "control room, training on Cook Nuclear Plant Unit 2 simulator would not be likely to result in an operator error resulting in a challenge to a critical safety function in Unit 1.
Design changes specific to Unit 1 will be reviewed to ensure no differences exist between the simulator and Unit 1 that,.would affect the ability for safe operation of Unit 1.
2.
A review was performed of all Unit 1 plant condition reports with training qualification methods/content causal codes with operations identified as the involved department.
This review identified no cases in which training on the Unit 2 simulator resulted in an error in operation of Unit 1.
Attachment to AEP:NRC:1134A Page 4
3.
Both units use Westinghouse Owners Croup based emergency operating procedures (EOPs) and in September 1993 both unit' abnormal operating procedures (AOPs) were standardized to the EOP two column format. Except for some set point differences between
- units, these procedures are virtually identical between units.
Extensive training was performed on the simulator in the use of the new AOPs.
4.
During the four-year period from initial certification to present, Unit 1 had fewer reactor trips than Unit 2 (two trips on Unit 1 vs nine on Unit 2).
A review of trip causes showed no operator error induced trips on Unit 1 and only one on Unit 2 in which operator action was contributory. This data shows that not performing Unit 1 specific simulator training had no significant impact on normal operating performance.
5.
During the four-year period from initial certification to present, Unit 1 set a plant operating continuous run record of 470 days.
6.
Where design changes affect both units, installation on the simulator is completed prior to installation in either Cook Nuclear Plant unit when training could be enhanced and overall plant operation improved.
An example of this philosophy is that a major modification consisting of replacement of Foxboro H Line equipment with Taylor Mod 30 controllers was performed during the 1994 Unit 1 refueling outage. This modification was installed on the simulator in October
- 1993, training was conducted on the simulator. relative to the new controllers, and an essentially error free startup was conducted on Unit 1 at the completion of the outage.
This modification is scheduled for Unit 2 in September 1994.
E.
Implementation Requirement
¹1:
Uncorrected performance tests failures and a
schedule for correction of such performance failures.
Refer to Cook Nuclear Plant Simulator Four Year Report Unit 2 for a list of performance test failures and scheduled correction dates.
Attachment to AEP:NRC:1134A Page 5
Requirement ¹2:
Description of performance testing performed in the last four-year period.
No performance testing was performed specific to the Unit 1 "training load" during the last four year period. Performance testing of the simulator was performed in accordance with t'e testing schedule per the original certification submittal on Unit 2 "training load". Refer to Cook Nuclear Plant Simulator Four-Year Report Unit 2 for performance testing abstract and completion dates.
Requirement ¹3:
Description of performance tests, if different, to be conducted on the simulation facility during the subsequent four year period.
Refer to Cook Nuclear Plant Simulator Four Year-Report Unit 2, (pages 26 thru 34) for a complete list of certification tests to be performed on the simulator in the next four-year period.
New tests added to the simulator include:
CC10:
CCW Inleakage to RCP Lower Bearing Oil Reservoir RC12:
RCP Lower Bearing Oil Reservoir Leak RC29:
Steam Generator Blowdown Leak Upstream of Containment Isolation Vlv RM03 Eberline Radiation Monitor Failures RP21: Failure of Feedwater Isolation to Occur RX29:
Feedpump Discharge Pressure Transmitter (FPC-250)
Failure TRANSIENT ll:
Load Rejection Requirement
¹4:
Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.
No performance testing willbe performed specific to a Unit 1 "training load" per "D. Discussion" above.
Refer to Cook Nuclear Plant Simulator Four-Year Report Unit 2 (pages 26 thru
- 34) for the schedule of certification testing to be performed over the next four-year period on the Unit 2
"training load". Approximately 25% of all malfunction testing is scheduled annually.
NRC RM 474 lthptg U.
LSD REOlJLA R
COMMl88IOig SIMULATIONFACILECERTIFlCATION Page 6/'pRDYED b
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COOK NUCLEAR PLANT eo-316 INDIANAMICHIGAN POWER COMPANY 8/24/94 This le le eoday tlat
- t. Tho aadee nafned leeaay xooneeo te eeetng a fnedaxon lecÃIIyoonAdng eofolyof a tanaleferenoed ebnotel er the tasets lhe tettueenentko ot 10 opft boAE.
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XL TMe stmvhlxst teoaty tnoste a E~~ ln AfxoIAMILadL Taaa. ae endoleod hy NRO gotstoIy aobfo a1XL xthoeaaro eny xxoxpttoNbtothooedwoatfonat thte bee,cttEcxNERE { ) snd cteacethehgtf on addtfohH pageoaahsoeeearr.
HAIXE(erother fdonttostan) AMOLOCAllOHOF tVLLVLATtQMFAOUTY.
COOK NUCLEAR PLANT TRAINING CENTER ONE COOK PLACE BRIDGM4N, MI 49106 atteLATLQHFArXLrrYPERFOfadANCETEIT AfftrfRacrfrATT~ sparred Hers ~fn fh ~H~m w dM e'er, ea 6 QEacf~oH oF pERFQfoAAMQETEsTLMQ cQMpLETEQ. faaooh eddprend~
ae eosssery ~fdenhy ths acne doentpdsn aotxl~p See attached, Cook Nuclear Plant Simulator Four Year Report Unit Two, paZes 12 thru 25.
afLXAATtDNFAcxrTYpERFofoJIAHQETEfrttnooQHEovLEATTAOMEL rrarrw sendIrotoreppraefseetsrlxa ofpsrfomtenootests per gearaerho Jbcoteerporfedoemmsnobgnfrb ate dMs ofNsesrtft~
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See attached, Cook Nuclear Plant Simulator Four Year Report Unit Tvo, pages 26 thru 34.
pEFFQRfaaMQETEtrttHO pLANCHANOE. ffsrenf rnodlfsecaeo be a pedeneaeeo ferfhffpfen eobmaeed one~ oentessdsrcg QEXQfapITQH oF FEFFQRMAMQE TEBfoto pLANQttAHDE fcxeeh edddenef popes as nooooeery end Afsnteyw gem onetafen aefng eendnoedg New performance'ests added to the testing schedule include:
CC10:
CCW Inleakage to RCP Lower RC29:
Steam "Generator Blowdown Leak Upstream Bearing Oil Reser'vior.
of Containment Isolation Ualve.
RC12:
RCP Lover Bearing Oil RP21:
Failure of Feedvater 'Isol. to Occur.
Reservior Leak.
RX29:
Feedpump Discharge Pressure Transmitter RM03:
Eberline Rad. Monitor Failures
~SI QP(1250( Fgipure.
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Attachment to AEP:NRC:1134A Page 7
DONALD C.
COOK NUCLEAR PLANT SIMULATOR FOUR-YEAR REPORT UNIT TWO A.
Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 50.55 Subpart E, Section 55.45.
To comply with 10 CFR 55.45, a report to the Commission which identifies simulator testing status must be submitted by the fourth anniversary of original certification. The purpose of this report is to satisfy this reporting requirement for the Cook Nuclear Plant simulator.
B.
References Title 10, Code of Federal regulations, Part 55,
'Operator Licenses',
Subpart E, Section 45.
2.
U.
S. Nuclear Regulatory Guide 1.149
'Nuclear Power Plant Simulation Facilities for use in Operator License Examinations.
3.
- 1985,
'Nuclear Power Plant Simulators for use in Operator Training.
C.
Reporting Requirements The requirements of this report as outlined in 10 CFR 50.55 are:
Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any.
Subpart E, Section 55.45 (b)(5)(ii).
2.
A description of performance testing completed for the simulation facility.
Subpart E, Section 55.45 (b)(5)(vi).
Attachment to AEP:NRC:1134A Page 8
3.
A description of the performance tests, if different, to be conducted on the simulation facility during the subsequent four-year period.
Subpart E, Section 55.45 (b)(5)(vi).
- 4. A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.
Subpart E, Section 55.45 (b)(5)(vi).
D.
Implementation Requirement
¹1:
Uncorrected performance tests failures and a
schedule for correction of such performance failures.
Uncorrected performance test failures include:
DR 93413 and 94068:
Slight Tave increase following reactor trip.
This increase is extremely short in duration and has very little training impact.
DR 94074:
Pressurizer surge line temperature response is too rapid with pressurizer insurge and outsurge conditions.
DR 94078:
Identify reason for and correct as necessary containment pressure spikes during large break LOCA.
DR 94066: Main generator seal oil response is incorrect when a seal oil leak is inserted.
DR 94128:
Condenser Delta T values do not match plant information at low power.
DR 94214: Auxiliary feed line leak would not isolate properly.
A DR 94252:
Reactor head leak is collected in the wrong containment sump.
These DR' are scheduled for completion within one year of origination dates.
DR 93413 DR 94068 DR 94074 DR 94078 DR 94066 DR 94128 DR 94214 DR 94252 Completion Completion Completion Completion Completion Completion Completion Completion date:
date:
date:
date:
date:
date:
date:
date:
11/08/94 01/24/95 01/27/95 01/31/95 01/22/95 03/31/95 06/04/95 08/13/95
Attachment to AEP:NRC:1134A Page 9
Requirement 82:
Description of performance testing performed in the last four-year period.
ANSI 3.5, 1985 Appendix A lists the requirements relative to certification testing for nuclear plant simulators.
These requirements fall into four separate categories.
Computer Real Time Test-verification of real time simulation by the simulator.
2.
Steady State and Normal Plant Evolution Performance Tests a)
Steady State Tests-verification of simulator stability and verification that process parameter values reflect actual reference plant values.
b)
Normal Plant Evolutions Performance Tests-verification of simulator ability to perform in accordance with reference plant operating procedures.
3.
Transient tests-verification of simulator' ability to reproduce defined transients Malfunction testing-testing of each generic malfunction to verify simulator response and system interaction.
Computer Real Time Test.
ANSI 3.5, 1985 requires real time verification to ensure the simulation dynamic performance is in the same time base relationships, sequences, durations, rates and accelerations as the dynamic performance of the reference plant.
The Cook Nuclear Plant simulator uses Real Time Executive Tasks (RTEX) to ensure that the simulator remains in real time during all simulation.
This task uses a frame counter routine to ensure an overtime abort and'imulator 'reeze'ondition occurs if the Real Time Executive Task fails to execute in allotted time period.
Simulator real-time tests have been performed annually with no failures identified.
See pages 12 thru 25 for test performance dates.
Attachment to AEP:NRC:1134A Page 10 Steady State and Normal Plant Evolutions Testing.
To ensure compliance with the standard regarding simulator steady state operation, the simulator has been operated at one hour intervals without operator action at power levels of 30%,
60%,
90%,
and 100% as per the original certification testing schedule.
Computed values were collected at half second intervals over the one hour time period for each power level.
This data has been verified accurate against actual plant data and heat balance information to be within the tolerances for critical and non-critical parameters as established in ANSI 3.5, 1985.
This data has also been plotted and verified not to vary more than 2% from initial values.
Refer to page 16 for steady state test abstract and completion dates.
Normal plant evolutions are tested and verified against the criteria established in ANSI 3.5 Section 3.1.1 annually per original certification schedule.
These tests are performed in accordance with approved plant procedures as listed on page 15.
In addition to testing performed by simulator personnel, these evolutions have been tested as an integral step of the Reactor Operation Replacement training program.
This program involves continuous operation (per approved plant procedures) of the simulator from full power to half loop conditions, and from half loop back to full power operation by instructors and SRO candidates with numerous years of plant operating experience.
ANSI 3.5 tests not listed or performed on a regular schedule are clarified below.
Core performance testing (3.1.1.9) is performed on the simulator when core cycle upgrades are made on the simulator (same cycle as the reference plant).
Operations surveillance tests (3.1.1.10) are performed on an as needed basis within the operations training program using approved plant procedures.
Transient Testing.
All transient tests required by ANSI 3.5, Appendix B section B.2.2 have been conducted on the simulator per the original certification schedule.
Attachment to AEP:NRC:1134A Page 11 The data collected in the performance of these tests is collected at one half second intervals and has been compared to actual data where existing data was available.
These tests have been reviewed by a team of subject matter experts made up of operations and simulator personnel.
Refer to pages 17 and 18 for transient test abstracts and completion dates.
Malfunction Testing.
The Cook Nuclear Plant simulator has 310 malfunctions used to introduce transients and/or faults into the simulator for operator training.
All malfunctions have been tested in the previous four year period with approximately 258 tested annually.
Refer to pages 19 thru 25 for malfunction test abstracts and completion dates.
Requirement ¹3:
Description of performance tests, ifdifferent, to be conducted on the simulation facility during the subsequent four year period.
Refer to pages 26 thru 34 for a complete list of certification tests to be performed on the simulator in the next four year period.
New tests added to the simulator include:
Load Rejection CC10:
CCW Inleakage to RCP Lower Bearing Oil Reservoir RC12:
RCP Lower Bearing Oil Reservoir Leak RC29:
Steam Generator Blowdown Leak Upstream of Containment Isolation Vlv RM03: Eberline Radiation Monitor Failures RP21: Failure of Feedwater Isolation to Occur RX29: Feedpump Discharge Pressure Transmitter (FPC-250)
Failure TRANSIENT 11:
Requirement
¹4:
Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.
Pages 26 thru 34 outline the schedule for certification testing to be performed over the next four year period.
Approximately 25% of all malfunction testing is scheduled annually.
Attachment to AEP:NRC:1134A Page 12 DONALD C.
COOK NUCLEAR PLANT SIMULATOR CERTIFICATION TESTING The following pages consist of testing information relative to'he Cook Nuclear Plant simulator certification requirements.
The sections are:
Computer Real Time testing Normal Plant Evolution (NPE) testing Steady State Testing Transient Testing Malfunction testing All testing has been completed per requirements of ANSI 3.5, 1985 as amended by Regulatory Guide 1.149.
Deviations from test schedule submitted in the original certification report follow.
Special Transient Test ST-3 scheduled for completion in third quarter of 1991 was not completed or all data pertaining to the test was lost.
Test was not identified as being delinquent until it became due in the third quarter of 1992.
This is an in-house test and not a requirement of ANSI 3.5 appendix A.
Special Transient Tests ST-1 and ST-2 and Steady State Test SS-Ol scheduled for completion in the first and second quarters of 1991 were not completed until the fourth quarter of same year.
Review of yearly test'ompletion identified incomplete tests and they were immediately rescheduled.
Special Transient Tests ST-4 scheduled for completion in the fourth quarter of 1992 was not completed until January 15, 1993.
Test data review identified plant data corresponded to 90%. thermal
- power, original test performed as scheduled was run at 100$
power.
Test was immediately rescheduled and completed at the proper power level.
Malfunction Tests
- ED12, ZA04,
- RH07, TC12, RMOl scheduled for completion in the first and second quarters of 1991 were completed in the fourth quarter of 1991.
Test review identified no documentation of these tests as being performed and they were immediately rescheduled.
Attachment to AEP:NRC:1134A Page 13 Malfunction test RP12 was not performed in the fourth quarter of 1990.
Test was inadvertently scheduled for both the third and fourth quarters of 1990.
Test was completed as scheduled in the third quarter.
Malfunction test CC08 scheduled for completion in second quarter of 1992 was completed in the first quarter of 1992 as part of additional simulator testing.
Malfunction test FW49 scheduled for completion 'in the first quarter of 1993 has been deleted.
Attachment to AEP:NRC:1134A Page 14 COOK NUCLEAR PLANT SIMULATOR REAL TIME TEST REPORT TEST RO.
CRT-1 CRT-1 CRT-1 CRT-1 COMPUTER REhL TIME TEST COMPUTER REhL TIME TEST COMPUTER REhL TIME TEST COHPUTER REhI TIHE TEST MTE 11/05/91 01/04/92 03/12/93 01/12/94
Attachment to AEP:NRC:1134A Page 15 COOK NUCLEAR PLANT SIMULATOR NORMAL.PLANT EVOLUTION PERFORMANCE TESTING DEQRIPZION NPE-1 NPE-2 NPE-3 NPE-4 NPE-5 NPE-6 NPE-7 RCS FILL AND VENT RCS FILL AND VENT RCS PILL AND VENT RCS PILL AND VENT HEATUP FROH BODE 5 TO HODE 3 HEATUP FROM NODE 5 TO BODE 3 HEATUP FRCH MDE 5 TO BODE 3 HEATUP FROH NODE 5 TO BODE 3 REACTOR STARTUP REACTOR STARTUP REACTOR STARTUP POWER ESCALATION POWER ESCALATION POWER ESCALATION POWER REDUCTION POWER REDUCTION POWER REDUCTION POWER REDUCTION PLANT COOLDOWN PLANT COOLDOWN PLANT COOLDOWN RCS DRAIN TO HALF LOOP RCS DRAIN TO HALF LOOP RCS DRAIN TO HALF LOOP 02-OHP-4021. 002. 001 02-OHP-4021. 002. 001 02-OHP-4021.002.001 02-OHP-4021.002.001 02-OHP-4021.001.001 02-OHP-4021.001.001 02-OHP"4021.001.001 02-OHP-4021.001.001 02-OHP-4021.001.002 02-OHP-4021.001.002 02-0HP-4021.001.002 02"OHP-4021. 001. 006 02-0HP-4021.001.006 02-0HP-4021.001.006 02-OHP-4021. 001. 003 02-0HP-4021.001.003 02-OHP"4021.001.003 02-0HP-4021-001.003 02-OHP"4021.001.004 02-0HP-4021.001.004 02-0HP-4021.001.004 02-OHP-4021.002.005 02-0HP-4021.002.005 02-OHP-4021.002.005 03/31/81 01/04/92 02/07/93 01/17/94 06/30/91 04/12/92 06/11/93 06/26/94 09/30/91 04/18/92 09/23/93 12/31/91 10/23/92 11/19/93 06/28/91 04/16/92 05/28/93 06/27/94 09/30/91 06/20/92 09/10/93 12/31/91 12/12/92 12/15/93
Attachment to AEP:NRC:1134A Page 16 COOK NUCLEAR PLANT. SIMULATOR STEADY STATE TESTING REPORT TEST HO.
SS-01 SS-01 SS-01 SS-01 SS-02 SS-02 SS-02 SS-02 SS-03 SS-03 SS-03 SS-04 SS-04 SS-04 TZTIZ 30X POHER STEADY STATE TEST 30Z POHER STEADY STATE TEST 30Z POHER STEADY STATE TEST 30X POWER STEADY STATE TEST 60Z POWER STEADY STATE TEST 60Z POWER STEADY STATE TEST 60Z POHER STEADY STATE TEST 60Z POHER STEADY STATE TEST 90X POWER STEADY STATE TEST 90X POHER STEADY STATE TEST 90X POHER STEADY STATE TEST 100Z POHER STEADY STATE TEST 100Z POHER STEADY STATE TEST 100X POWER STEADY STATE TEST 12/07/91 03/26/92 03/16/93 03/28/94 06/27/91 06/24/92 06/18/93 06/26/94 07/22/91 08/28/92 09/20/93 12/07/91 12/29/92 11/30/93
Attachment to AEP:NRC:1134A Page 17 COOK NUCLEAR PLANT SIMULATOR TRANSIENT TESTS DESCRIPTION TRANSIENT 01 TRANSIENT 01 TRANSIENT 01 TRANSIENT 01 TRANSIENT 02 TRANSIENT 02 TRANSIENT 02 TRANSIENT 02 TRANSIENT 03 TRANSIENT 03 TRANSIENT 03 TRANSIENT 04 TRANSIENT 04 TRANSIENT 04 TRANSIENT 05 TRANSIENT 05 TRANSIENT 05 TRANSIENT 05 TRANSIENT 06 TRANSIENT 06 TRANSIENT 06 TRANSIENT 06 TRANSIENT 07 TRANSIENT 07 TRANSIENT 07 TRANSIENT 08 TRANSIENT 08 TRANSIENT 08 TRANSIENT 09 TRANSIENT 09 TRANSIENT 09 TRANSIENT 09 TRANSIENT 10 TRANSIENT 10 TRANSIENT 10 TRANSIENT 10 MANUAL REACTOR TRIP MANUAL REACTOR TRIP MANUAL REACTOR TRIP MANUAL REACTOR TRIP TRIP OF ALL MAIN PEEDPUMPS TRIP OF ALL HAIN FEEDPUMPS TRIP OF ALL MAIN FEEDPUMPS TRIP OF ALL MAIN PEEDPUMPS CLOSURE OF ALL MSIV'6 CLOSURE OF ALL HSIV'S CLOSURE OF ALL HSIV'S TRIP OF ALL RCP'S TRIP OF ALL RCP'S TRIP OF ALL RCP'S TRIP OF RCP f23 TRIP OF RCP f23 TRIP OF RCP f23 TRIP OF RCP f23 MAIN TURBINE TRIP W/O RX TRIP MAIN TURBINE TRIP W/0 RX TRIP HAIN TVRBINE TRIP W/0 RX TRIP MAIN TURBINE TRIP W/O RX TRIP MAX POWER RAHP 100X-752-1002 MAX POWER RAMP 100X-75X-IQQX MAX POWER RAMP 100X-752-1002 MAX SIZE LOCh WITH BLACKOUT HAX SIZE LOCA WITH BLACKOUT HAX SIZE LOCA WITH BLACKOUT HAX SIZE MAIN STEAHLINE RUPTURE MAX SIZE HAIN STEAMLINE RUPTVRE HAX SIZE MAIN STEAHLINE RUPTURE MAX SIZE HAIN STEAHLINE RUPTURE SLOW RCS DEPRESSURIZATION TO SATURATION SLOW RCS DEPRESSURIZATION TO SATVRATION SLOW RCS DEPRESSURIZATION TO SATURATION SLOW RCS DEPRESSURIZATION TO SATVRATION 04/05/91 02/17/92 03/12/93 01/22/94 06/17/91 06/22/92 06/11/93 06/26/94 10/23/91 08/28/92 09/23/93 11/16/91 10/26/92 10/26/93 04/05/91 02/17/92 03/12/93 01/22/94 06/17/91 06/22/92 06/21/93 06/26/94 11/16/91 08/28/92 09/17/93 12/10/91 10/26/92 12/06/93 04/05/91 02/17/92 03/12/93 01/21/94 06/17/91 10/26/92 06/14/93 06/26/94
Attachment to AEP:NRC:1134A Page 18 COOK NUCLEAR PLANT SIMULATOR SPECXAL TRANSXENT TESTXNQ TEST NUMBER DESCRIPTION ST-01 ST-01 ST-Ol ST-01 ST-02 ST-02 ST-02 ST-02 ST-03 ST-03 ST-04 ST-04 ST-04 NATURAL CIRC.
COOLDOWN W/VESSEL HEAD VOID FORMATION NATURAL CIRC.
COOLDOWN W/VESSEL HEAD VOID FORMATION NATURAL CIRC, COOLDOWN W/VESSEL HEAD VOID FORMATION NATURAL CIRC.
COOLDOWN W/VESSEL HEAD VOID FORMATION ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
STEAM GENERATOR TUBE RUPTURE STEAM GENERATOR TUBE RUPTURE UNIT 2 REACTOR TRIP, NOVEMBER 13, 1885 UNIT 2 REACTOR TRIP ~
NOVEMBER 13 y 1885 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1985 12/30/91 02/25/92 03/12/93 03/30/94 12/09/91 06/24/92 06/11/83 06/10/84 08/28/92 09/24/93 12/30/91 01/15/93 12/06/93
Attachment to AEP:NRC:1134A Page 19 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT YEAR 1990 1990 1990 1990 1990 1990 1990 1990 1990 1890 1990 1990 1990 1990 1990 1990 1990 1980 1990 1990 1990 1980 1980 1990 1990 1990 1980 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 CC02 CC06 CH01 CS03 CV04 CV09 CV13 CV17 CV26 CV31 CW02 ED03 ED06 ED07 ED11 ED15 ED16 ED19 ED20 ED24 EG03 EG07 EG11 EG15 FP05 FW05 FW16 FW22 FW26 FW30 FW34 FW36 FW42 FW46 FW50 FW54 FW56 MS03 MS06 MS12 MS17 NI02 NZ06 NI10 NI14 RC03 RC07 RC13 RC17 RC24 RC26 RD04 RD06 RD12 CCW PUMP FAILURE TO AUTO START SEAL WATER HX TUBE LEAK CONTAIN~
PRESS.
RELIEF VLV PAILURE REFUELING WATER STORAGE TANK LEAK LETDOWN LINE ORIFICE ISO. VLV FAILURE LETDOWN TEMPERATURE CONTROL FAILURE CHARGZNG PUMP TRIP VOLUME CONTROL TANKL~
REACTOR COOLANT PUMP fl SEAL FAILURE BACKPRESSURE CONT VLV FAILURE-QRV"200 CW PUMP DISCHARGE VALVE FAILURE LOSS OF RESERVE AUXILIARYTRANSFORMER LOSS OF 600 VAC BUS LOSS OF 460 VAC BUS LOSS OF 250 VDC BUS LOSS OF VITAL INST BUS STATIC SWITCH AUXILIARIESAUTO BUS TRANSPER FAILURE ELECTRICAL GRID LOAD REJECTION ANN PANEL POWER SUPPLY FAILURE LOSS OF 250 VDC TRAIN "N" BATTERY MG AUTO VOLTAGE REG FAILURE TO MANUAL DG SPEED CONTROL FAILURE DIESEL GENERATOR FAILURE TO TRIP MG SEAL OIL UNIT PIPING RUPTURE CONTROL ROOM CABLE VAULT PIRE MAIN FEEDPUMP TURBINE TRIP HP HTR 46 LVL CONTROL VALVE FAILURE HP HTR f5 LVL CONTROL VALVE FAILURE LP HTR f4 LVL CONT TRANSMITTER PhIL LP HTR g3 LVL CONTROL VALVE FAILURE CONDENSATE BOOSTER PUMP TRIP LOSS OP CONDENSER VACUUM CONDENSATE STORAGE TANK LEAK AUX FEEDPUMP TRIP TDAFW PUMP SPEED CONTROLLER FAILURE FDWTR RUPT OUTSIDE CONTAINMENT FEED PUMP STEAM SUPPLY CONT FAILURE MAZN STM LINE BREAK OUTSIDE CONT SG STOP VALVE DRIFTS SHUT MSR DRAIN TK ALT DRAIN LVL CONT FAIL STEAM SEAL CONTROLLER OSCILLATION SOURCE RANGE HV FAILURE TO DEENERGIZE INTERMEDIATE RANGE MONITOR FAILURE POWER RANGE CHANNEL FAILURE INTERMEDIATE RANGE CHANNEL BLOWN FUSE RCS LEAK REACTOR COOLANT PUMP LOCKED ROTOR RCP UPPER BEARING OIL RESERVOIR LEAK PRESSURIZER PORV FAILURE STEAM GENERATOR TUBE LEAK PRESSURIZER INSTRUMENT LINE LEAKAGE STUCK CONTROL ROD (UNTRIPPABLE)
IN-HOLD-OUT SWITCH FAILURE FAILURE OF CONTROL RODS TO MOVE 09/05/90 09/05/90 10/01/90 10/01/90 10/01/90 ll/13/90 10/01/90 10/01/90 10/02/90 10/03/80 09/05/80 10/02/90 03/25/90 11/21/90 03/25/90 03/25/90 10/03/90 07/16/90 09/06/90 09/07/90 09/07/80 10/03/90 09/11/90 09/11/90 09/11/90 10/03/90 09/12/90 09/24/80 10/24/80 1O/24/8O 10/23/90 09/13/90 09/24/90 09/24/90 09/24/90 04/09/90 09/24/90 10/24/90 10/24/90 12/27/90 09/24/90 12/27/90 09/24/90 ll/12/90 11/13/90 09/24/90 11/13/90 11/13/90 11/14/90 09/25/90 11/13/90 09/25/90 09/25/90 11/14/90
Attachment to AEP:NRC:L134A Page 20 COOK NUCLEAR PLANT SIMJLATOR MALPUNCTXON TEST REPORT YEAR 1990 1000 1990 1SSO 1080 1090 1990 1990 1090 1080 1090 1090 1090 1990 1890 1090 1890 1990 1990 1090 1990 1090 1990 1SQO 1990 1001 1991 1S91 1881 1991 1091 1901 lQS1 1991 1991 1001 1991 1991 1801 1091 1901 1091 1091 1091 1991 10Sl 1091 1991 1901 1991 1991 1091 1991 1991 RD16 RH02 RH06 RH11 RH15 RP03 RP08 RP12 RP16 RP20 RX04 RX08 RX12 RX16 RX20 RX24 RX27 RX28 SH01 SH05 TC02 TC06 TC11 TP02 TUQ3 CC03 CC07 CH02 CS04 CV05 CV10 CV14 CV20 CV27 CV32 CH03 ED04 ED21 EG04 EGOS EG12 FP01 FM01 FH06 FM15 FH19 PH23 FH27 FH31 FH35 FH39 FH43 FH47 FH51 TITLE IRPZ FAILURE RHR PUMP SEAL FAILURE RHR INJ HDR RELIEF VALVE FAIL (SV-1Q4)
RHR RET FLOH TRANS FAILURE (IFI 335)
SI ACCUMULATOR N2 PRESSURE LOSS PAILURE OF REACTOR TRIP BREAKER SPVRIOUS FEEDHATER ISOLATION TRIP SPURIOUS ACTUATION OF SZ FAILURE OF CI PHASE B TO AUTO ACTUATE TRAIN "B" K600 RELAY FAILURES PRESSURIZER PRESSURE TRANS FAILURE PZR SPRAY UALVE AUTO CONTROL PAILURE MS RELIEF VLV CONTROLLER OSCILLATION STEAM DUMP "PRES CONT" ERRATIC OPS SG STEAM FLOH TRANSMITTER PAILURE FH CONTROL VALVE CONTROLLER PAILVRE FEED PUMP DP CONTROLLER PAILURE LOSS OF 480V MOC NON ESSENTIAL SERVICE MATER PUMP TRIP ESH PIPING RUPTURE MAIN TURBINE FAILURE TO TRIP MAIN TURBINE ERRATIC CONTROL VALVE AUTO LOAD SET OSCILLATION TVRBZNE AUX COOLING PIPING RUPTURE MAIN TURBINE HIGH UIBRATION CCMPONENT COOLING MATER RUPTURE COMPONENT COOLING HX TUBE RUPTURE CONTAIN. PRESSURE TRANSMITTER FAILURE RHST LEVEL TRANSMITTER FAILURE LETDOHN HEAT EXCHANGER TUBE LEAK NORMAL CHG LINE LEAK INSIDE CONTAIN CHARGING PUMP SUCTION LINE LEAKAGE INADVERTENT BORATZON Rl~MTOR COOLANT PUMP 42 SEAL FAILURE PH FLOH TRANSMITTER (QFC 422) FAILURE TRAVELING HATER SCREEN FOVLING LOSS OF EP SUPPLY TRANS TR-12 EP 4KV/600V AUX TRANSFORMER LOSS MG AUTO VOLTAGE REGVLATOR FAILURE DG SPEED GOVERNOR FAILURE DG OUTPUT PREAKER FAILURE TO AUTO CLS PIRE PROTECTION SYSTEM RUPTURE MAIN FEEDHATER RUPTVRE AT SG INLET MFP TURBINE SHEARED SHAFT (UNRECOU)
FEEDHATER CONTROL UALVE FAILURE HP HEATER f6 TUBE RUPTURE
=- HP HEATER f5 TUBE RUPTURE LP HTR 44 LVL CONTROL UALVE FAILURE LP HEATER f3 TUBE RUPTURE COND BOOSTER PP DISC PIPING RUPTVRE CONDENSER TUBE LEAK HEATER DRAIN PUMP TRIP AUX FEEDPVMP SUCTION LINE LEAKAGE TDAFP TRIP A THROTTLE VALVE FAILURE 11/21/00 09/25/90 12/27/00 09/25/90 11/21/90 00/25/00 00/25/90 00/26/00 09/26/00 00/27/00 12/27/90 11/14 ISO 12/27/00 12/27/90 12/27/90 11/14/90 07/10/00 00/26/90 09/26/00 09/26/SO 11/14/80 09/26/90 12/26/80 12/26/00 00/26/90 09/18/91 02/16/91 05/15/91 11/13/91 02/16/01 07/02/01 10/23/01 02/16/91 05/15/91 07/10/01 05I15/81 10/24/01 09/12/91 02/16/01 05/15/01 09/12/01 10I23/91 11/13/01 02/16/01 02/16/91 05/15/01 07/10/01 05/15/91 11/13/91 07/10/01 11/13/01 02/18/91 05/16/81 07/19I91
Attachment to AEP:NRC:1134A Page 21 COOK NUCLEAR PLANT SIMULATOR MAL1WNCTXON TEST REPORT 1081 1001 1091 1001 1001 1091 1091 1001 1991 10S1 1901 1991 1001 1001 1091 1991 1091 1001 1001 1001 1S91 1091 1901 1991 1901 1991 1001 1901 1001 1001 1S91 1091 1891 1891 1991 1081 1991 1091 1901 1091 1001 1091 1001 1002 1892 109R 1002 1082 1092 1882 1092 1082 1092 1992 IA01 IA05 HS04 HSQQ HS13 MS16 NI03 NI07 NI11 NI15 RC04 RC06 RC14 RC10 RC25 RD01 RD05 RDOQ RD13 RD1'7 RH03 RH07 RH12 RM01 RP05 RP09 RP13 RP17 RXO1 RX05 RXQS RX13 RX17 RX21 RX25 SI01 SW02 SW06 TCQ3 TC07 TC12 TP03 TU05 CCQ4 CC08 CS01 CV01 CV06 CV11 CV15 CV21 CV28 CV33 ED01 PLANT AIR COMPRESSOR TRIP CONT AIR SYS RUPTURE IN CONTAINMENT HS LINE BREAK DOWNSTREAM SG STOP VLVS HSR TUBE RUPTURE HSR DRAIN TK ALT LVL CONT VALVE PhIL STEAM DUMP CONTROL VALVE PAILURE INCORRECT SR CHANNEL RESPONSE IR IMPROPER COHPENSATION PR CHANNEL OUTPUT OSCILLATION POWER RANGE CHANNEL BLOWN FVSE PRESSURIZER SURGE LINE LEAK REACTOR COOLANT PUHP SHAFT BREAK PZR HIGH GAS CONCENTRATION IN VPR SP PRESSURIZER SAFETY VALVE FAXLURE SG BD LINE LK DOWNSTREAM CONT ISOL DROPPED CONTROL ROD EJECT OF RD WITH RVPT MECH HOUSING UNCONT ROD MOTION DEMAND (AUTOHATIC)
ROD GROUP FAILURE TO HOVE ROD GROUP STEP COUNTER FAILURE RHR HX BYPASS FLOW CONTROL VALVE PhIL RHR NORMAL CD SUC LINE LK INSIDE CONT SI LOOP CHECK VALVE LEAKAGE AREA RADIATION MONITOR FAILURE REACTOR (XX)LANT FMW TRANS FAILURE FAILURE OF FW ISOLATION TRIP TO OCCUR FAILURE OF CI PHASE A TO AUTO ACTUATE FAILURE OF CI PHASE B TO HANUAL ACT RCS HOT LEG PRESSURE TRANS FAILVRE PZR LVL TRANS FAILURE (PROT C)(ANNEL)
PZR PRES MASTER CONXROLLER FAILURE STEAH DUMP "TAVG" CONTROLLER FAILURE SG PRESSURE TRANSMITTER FAILURE SG PEED FLOW TRANSHITTER PAILURE FEEDWATER CONTROL VALVE OSCILLATION SAFETY INJECTION PUMP TRIP NESW PIPING RUPTURE IN 'XURB BLDG FP TURB OIL COOLING CONTROLLER FAILURE MAIN TURBINE AUTO TRIP FAILURE MAIN TVRBINE INTERCEPT VALVE FAILURE MAIN TURBINE SPEED SIGNAL FAILURE HG STATOR COOLING SYSTEH RUPTURE MAIN TURBINE BEARING FAILURE MISC CCW HDR RUPTURE INSIDE CONTAIN.
CCW LEAKAGE INTO RCP BRNG OIL RES.
CONTAINMENT SPRAY PUMP TRIP LETDOWN LINE RUPTURE INSIDE CONTAIN.
ORV-301 FAILURE NORMAL CHG LINE LEAK OUTSIDE CONTAIN VCT LEVEL CONTROL VALVE FAILURE INADVERTENT DILUTION REACTOR COOLANT PUMP f3 SEAL PAILURE Bh FLOW CONTROLLER (QFC-421)
FAILURE LOSS OF 345KV BUS NO.
1 02/18/01 11/13/01 03/16/91 05/16/01 07/26/01 05/16/81 ll/05/01 03/16/01 05I16I01 08/16/91 11/13/01 03/16I01 00/18/Sl 05/16/01 11/13/01 03I16I91 05/16/81 09/12/01 09/12/91 11/13/01 11/05I01 11/05/01 03/16I91 12/RO/91 05/16/01 07/10/01 11/13/01 03/16/01 05/17/01 07/00/01 11/05/01 03/16/91 05/16/01 07/00/01 11/05/91 09/12/Sl 03/16/01 05/17/91 11/05/01 11/10/01 11/05/91 05/17/91 07/10/91 03/23/02 02/24/02 06/02/02 08/17/02 11/R3/02 01/04/92 05/27/92 07/13/02 12/28/02 Ql/04/02 06/17/02
Attachment to AEP:NRC:1134A Page 22 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT 1902 1902 1002 1902 1992 1902 1002 1092 1092 1002 1092 1002 1002 1002 1092 1002 1002 1002 1092 1092 1002 1092 1002 1092 1092 1S02 1092 1992 1002 1992 1002 1092 1002 1092 1092 1992 1092 1902 1992 1002 1992 1902 1992 1092 1002 1002 1092 1092 1092 1092 1002 1092 1992 1092 ED10 ED22 EGOS EG09 EG13 FP02 FW02 FW07 FW16 FW20 FW24 FW28 FW32 FW36 FW40 FW44 FW48 FW52 ZA02 MS01 HS05 MS10 HS14 HS21 NZ04 NZ08 NI12 RC01 RC05 RC09 RC15 RC21 RC26 RD02 RD06 RD10 RD14 RD18 RH04 RH08 RH13 RM02 RP06 RP10 RP14 RP18 RX02 RX06 RX10 RX14 RX18 RX22 RX26 SI02 LOSS OP 120 VAC CONTROL ROOH POWER LOSS OF SWITCHGEAR CONT POWER TRAIN B HG OUTPUT BREAKER FAILURE TO TRIP DG VOLTAGE CONTROL FAILURE DG OUTPUT BREAKER FAILURE TO CLOSE INADV ACT OP CHARCOAL FILT PIRE PROT.
MFW RUPTURE BEFORE SG CHECK VALVE HAIN FEEDPUMP TURBINE BEARING FAILVRE HP HTR 46 LVL CONT TRANSHITTER FAIL HP HTR 45 LVL CONT TRANSHITTER FAIL HP HEATER g5 STEAH INLET RUPTURE I.P HEATER 44 TUBE RUPTURE LP HEATER f3 STEAH INLET RUPTVRE COND BOOSTER PP RECIRC VALVE FAILURE HOZWELL LEVEL CONTROLLER PAILVRE HEATER DRAIN PUMP BEARING FAILURE AVX FEEDPUMP AUTO START FAILURE STEAH BOUND APW PUMP PLANT AIR SYSTEH RUPTURE MS LINE BREAK AT SG EXIT HAIN STEAM POWER RELIEF VALVE LEAK HSR COIL DRAIN TAIlK LVL CONT FAILVRE HSR STEAM SUPPLY VALVE PAILURE AUX STH 150 0 HDR CONT VALVE FAILVRE SR ENERGIZATION AT POWER (P10 FAIIVRE)
PR CHANNEL UPPER DETECTOR FAILURE AVDIO COUNT RATE CHANIIEL FAILURE RCS COLD LEG LOOP RUPTURE REACTOR VESSEL HEAD FLANGE LEAK REACTOR COOLANT PUMP TRIP PRESSURIZER SPRAY VALVE FAILURE FRT RUPTURE DISC FAILURE FAILED PVEL ELEMENT BROKEN CONTROL ROD UNCONT ROD BANK CONTINUOUS WITHDRAWAL CR HOVE OPPOSITE TO DEMAND SIGNAL IMPROPER BANK OVERLAP ROD CONTROL HG SET TRIP RHR HX FLOW CONTROL VALVE PAILURE RWST SUPPLY LINE TO RHR PUMP RUPTURE SI ACC TANK CHECK VALVE LEAKAGE PROCESS RADIATION MONITOR FAILVRE SPURIOUS STEAH LINE ISOLATION FAILURE OF SZ TO ACTUATE-AUTOHATIC FAILURE OF CZ PHASE h TO MANUAL ACT SPURIOUS ACTUATION OF CI PHASE B RCS HOT LEG TEMP TRANS FAILURE (NR)
PZR CAL LEVEL TRANSHITTER FAILURE PZR WATER LEVEL CONT OSCILLATION STEAM DUMP "PRES" CONTROLLER FAILURE HS TURB BYPASS HDR PRESS TRANS FAILURE SG PROGRA)%ED LEVEL SIGNAL FAILURE FP TURBINE SPEED CONTROLLER FAILVRE SAPETY INJECTION PUMP SHEARED SHAFT 11/24/92 06/02/02 08/17/92 11/24/02 01/04/02 06/15/02 08/28/02 12/11/02 02/11/02 06/15/02 01/04/02 08/28/02 06/15/92 03/23/92 12/10/92 05/27/92 08/28/02 09/24/92 12/28/02 02/11/02 06/02/92 09/24/02 12/28/92 02/14/02 06/02/02 08/28/92 12/10/02 03/23/92 12/10/02 02/14/92 08/15/02 08/28/92 12/28/92 02/14/92 06/15/92 08/28/92 11/11/92 06/02/02 06/15/92 08/28/92 12/19/92 03/11/92 01/21/02 06/02/92 08/28/02 12/19/02 01/21/02 05/27/92 09/24/92 12/28/92 01/21/02 05/27/92 08/28/02 12/28/02
Attachment to AEP:NRC:1134A Page 23 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT TITLE 1992 1992 1992 1992 1992 1992 1992 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1893 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 SW03 SW07 TC04 TC09 TC13 TP05 TU06 CC01 CC05 CC09 CC10 CS02 CV02 CV08 CV12 CV16 CV25 CV30 CW01 ED02 ED05 ED08 ED12 ED13 ED14 ED17 ED18 ED23 ED25 ED26 EG01 EG06 EG10 EG14 FP03 FW03 FW12 FW17 FW21 FW25 FW29 FW33 FW37 FW41 FW45 ZA03 IA04 MS02 MS06 MS11 MS16 NI01 NI05 NI09 NESW RUPT ON LWR CONT VENT CLR SUP MT OIL TEMPERATURE CONTROLLER FAILURE MAIN TURBINE STOP VALVE FAILURE MAIN GENERATOR LOAD LIMITER PAILURE TURBINE RUNBACK PAILURE STATOR COOLING WTR SYS HIGH COND TURBINE BLADE EJECTION COMPONENT COOLING WATER PUMP TRIP MISC CCW HDR RUPTURE IN AUX BUILDING CCW.LEAK ON RHR PUMP SUPPLY LINE CCW INLEAKAGE INTO RCP LOWER BRNG OIL RSVR CONTAIN. SPRAY PUMP SUCTION BLOCKAGE LETDOWN I INE RUPTURE OUTSIDE CONTAIN.
LETDOWN LINE RELIEF VLV SV-51 LEAKAGE CCP FLOW CONTROL VALVE FAILURE VCT LEVEL TRANSMITTER FAILURE RCP THERMAL BARRIER HX RUPTURE REDUCED CCP CAPACITY CIRCULATING WATER PUMP TRIP LOSS OP AUXILIARYTRANSFORMER LOSS OF 4160 VAC BUS LOSS OF 600V MCC LOSS OF 250 VDC POWER (TRAIN h)
LOSS OF 250 VDC POWER (TRAIN B)
LOSS OF 250 VDC BATTERY CHARGER LOSS OF PLANT LIGHTING GRID VOLTAGE OSCILLATION LOSS OF SWITCHGEAR CONT POWER TRAIN h LOSS OF 765/345KV TRANSFORMER BANK f4 LOSS OF 765KV DUMONT LINE MAIN GENERATOR TRIP DIESEL GENERATOR TRIP DIESEL GENERATOR FAILURE TO START DG RUNNING RELAY FAILURE DIESEL GENERATOR ROCM C02 ACTUATION MFW RUPT BETWEEN PEEDFLOW ELMT & FRV FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK HP HTR I6 LVL CONTROLLER AUTO PAILURE HP HTR t5 LVL CONTROLLER AUTO FAILURE HOTWELL PUMP TRIP LP HTR I3 LVL CONT TRANSMITTER PhIL LP HEATER BYPASS VALVE FAILURE HOTWELL PUMP DISCHARGE PIPING RUPTURE HW LEVEL CONTROL TRANSMITTER FAILURE HEATER DRAIN PUMP ELO VLV PAILS OPEN CONTROL AIR COMPRESSOR TRIP CONT AIR SYS RUPT IN TURBINE BUILDING MAIN STEAM LINE BREAK AT SG EXIT STEAM GENERATOR SAFETY VALVE LEAK MSR COIL DRAIN TANK LVL CONT VLV FAIL STEAM SEAL CONTROLLER FAILURE SOURCE RANGE MONITOR FAILURE SOURCE RANGE CHANNEL SPIKES PR CHANNEL LOWER DETECTOR FAILURE 02/ll/92 06/15/92 08/26/92 08/26/92 12/19/92 12/26/92 02/14/92 02/27/93 04/26/93 08/24/93 11/23/93 11/20/93 02/24/93 04/26/93 09/15/93 11/20/93 02/16/93 06/30/93 08/19/93 11/20/93 06/25/93 06/25/93 06/27/93 08/27/93 08/27/93 08/27/93 09/03/93 02/27/93 09/03/93 09/13/93 04/26/93 09/13/93 11/20/93 02/27/93 05/31/93 08/24/93 ll/20/93 03/10/93 04/26/93 09/12/93 11/20/93 03/10/93 04/26/93 06/24/93 11/20/93 05/31/93 09/13/93 09/12/93 11/20/93 02/27/93 05/31/93 09/13/93 11/23/93 02/27/93
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Attachment to AEP:NRC:1134A Page 24 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST REPORT 1993 1893 1993 1983 1993 1993 1993 1983 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1893 1893 1893 1993 1993 1993 1893 1893 1993 1993 1983 1993 1893 1994 1994 1894 1994 1994 1994 1994 1994 1994 1984 1994 1994 1994 NI13 RC02 RC06 RC10 RC11 RC12 RC16 RC23 RC27 RC29 RD03 RD07 RD11 RD15 RD19 RH01 RH05 RH09 RH14 RM03 Z(P01 RP07 RP11 RP15 RP19 RP21 RX03 RX07 RX11 RX15 RX19 RX23 RX29 SZ03 SN04 TC01 TC05 TC10 TP01 TU01 HD01 CC02 CH01 CV04 CV13 CV17 CV31 ED02 ED06 ED11 ED15 EG07 EG15 FW16 SOURCE RANGE INSTRUMENT BLOHN FUSE RCS HOT LEG LOOP LEAK RCS EMERGENCY VENT LEAKAGE RCS COLD LEG LEAK REACTOR COOLANT PUMP HIGH VIBRATION RCP LONER BEARING OIL RESERVOIR LEAK PRESSURIZER STEAM SPACE MANNAY LEAK STEAM GENERATOR TUBE RUPTURE RTD BYPASS MANIFOLD FLOH DEGRADATION S/G BLOHDOHN LINE LEAK UPSTREAM OF CIV STUCK CONTROL ROD (TRIPPABLE)
UNCONT ROD BANK CONTINUOUS INSERTION AUTO CONTROL ROD SPEED PAILURE IRPI POHER LOSS IMPROPER ROD NORTH RHR PUMP TRIP RHR HEAT EXCHANGER TUBE LEAK RHR PUMP SUCTION PIPE RUPTURE SI ACCUMULATOR TANK LEVEL LOSS EBERLINE AREA RADIATION MONITOR FAILURES REACTOR TRIP ACB AUTO TRIP FAILURE FAILURE OF STEAM LINE ZSO TO ACTIVATE FAILURE OF SI TO ACTUATE-MANUALLY SPURIOUS ACTUATION OF CI PHASE h TRAIN "h" K600 RELAY FAILURES FAILURE OF FHI TRIP TO OCCUR RCS COLD LEG TEMP TRANS FAILURE (NR)
REDUCED PRESSURIZER HEATER CAPACITY SG RELIEF VALVE CONTROLLER FAILURE STEAM DUMP SYSTEM FAILURE TO RESPOND TURBINE IMPULSE TRANSMITTER FAILURE SG LEVEL TRANSMITTER FAILURE FPC-250 TRANSMITTER FAILURE HIGH HEAD SI LINE RUPTURE ESSENTIAL SERVICE RATER PUMP TRIP MAIN TURBINE TRIP MAIN TURBINE CONTROL VALVE FAILURE MAIN GEN OPERATING DEVICE FAILURE TURBINE AUX COOLING PUMP TRIP AUXILIARYLUBE OIL PUMP TRIP RELEASE OF RADIOACTIVE GAS FROM GDT CCH PUMP FAILURE TO AUTO START CONTAIN. PRESS.
RELIEP VLV FAILURE LETDOWN LINE ORIFICE ISO. VLV FAILURE CHARGING PUMP TRIP VOLUME CONTROL TANK LEhlGKE BACKPRESSURE CONT VLV FAILURE-QRV-200 LOSS OF AUXILIARYTRANSFORMER LOSS OF 600 VAC BUS LOSS OF 250 VDC BUS LOSS OP VITAL INST BUS STATIC SWITCH DG SPEED CONTROL FAILURE MG SEAL OIL UNIT PIPING RUPTURE HP HTR f6 LVL CONTROL VALVE FAILURE 05/31/93 09/12/93 11/22/93 09/13/83 02/27/93 11/13/93 05/31/83 09/13/93 11/23/93 11/13/93 02/24/93 05/31/93 06/24/93 11/22/93 12/13/93 03/01/93 05/31/93 06/24/93 11/23/93 11/29/93 02/16/93 05/31/93 06/26/93 11/22/93 03/10/93 11/13/93 04/21/93 09/12/93 11/29/93 03/Ol/93 05/31/93 09/13/93 12/10/93 02/24/93 04/26/93 09/12/93 11/23/93 03/01/93 04/26/93 09/13/83 11/23/83 01/12/94 04/04/94 04/04/94 04/04/94 04/04/94 04/04/94 01/12/94 01/15/94 01/15/94 01/22/94 04/04/94 01/22/94 01/17/94
Attachment to AEP:NRC:1134A Page 25 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST REPORT TITLE 1004 1004 1004 1904 1004 1004 1904 1904 1904 1904 1994 1004 1004 1004 1904 1004 1904 1004 1004 1004 1094 1004 1094 1094 1094 1004 1904 FH22 FW26 FW34 FH38 FW46 FH50 FH54 MS08 MS17 NI02 NI14 RC13 RC24 RC28 RD04 RH02 RH06 RH11 RP08 RP16 RX04 RX12 RX20 RX27 TC06 TC11 TP02 HP HTR 45 LVL CONTROL VALVE FAILURE LP HTR ga LVL CONT TRANSMITTER FAIL CONDENSATE BOOSTER PUMP TRIP LOSS OP CONDENSER VACUUM AUX FEEDPUMP TRIP TDAFH PUMP SPEED CONTROLLER PAILURE FINTR RVPT OUTSIDE CONTAINMENT SG STOP VALVE DRIFTS SHUT STEAM SEAL CONTROLLER OSCILLATION SOURCE RANGE HV FAILURE TO DEENERGIZE INTERMEDIATE RANGE CHANNEL BLOWN FVSE RCP UPPER BEARING OIL RESERVOIR LEAK STEAM GENERATOR TUBE LEAK PRESSURIZER INSTRUMENT LINE LEAKAGE STUCK CONTROL ROD (UNTRIPPABLE)
RHR PUMP SEAL FAILURE RHR INJ HDR RELIEF VALVE FAIL (SV-104)
RHR RET FLOW TRANS FAILURE (IFI-335)
SPVRIOUS FEEDWATER ISOLATION TRIP FAILURE OF CI PHASE B TO AUTO ACTUATE PRESSURIZER PRESSURE TRANS PAILURE MS RELIEF VLV CONTROLLER OSCILLATION SG STEAM FLOH TRANSMITTER FAILURE FEED PUMP DP CONTROLLER FAILURE MAIN TURBINE ERRATIC CONTROL VALVE
,AUTO LOAD SET OSCILLATION TVRBINE AUX COOLING PIPING RUPTVRE 01/17/94 o6/oa/oa 06/04/04 01/17/04 01/17/04 01/18/04 06/04/04 06/04/04 01/18/04 06/06/04 06/04/04 06/04/04 01/18/04 06/04/04 01/18/04 01/22/04 06/06/04 01/22/04 01/22/04 01/22/04 06/04/94 06/04/04 06/04/04 01/22/94 01/18/04 o6/oa/04 06/02/04
Attachment to AEP:NRC:1134A Page 26 DONALD C.
COOK NUCLEAR PLANT SIMULATOR CERTIFICATION SCHEDULE The following pages consist of the Cook Nuclear Plant Simulator Certification Test schedule through 1998.
This section describes testing for:
Testing required per Appendices A and B of ANSI 3.5, 1993 Malfunction Testing Test schedule has been modified from last report to include new malfunctions added to the simulator.
Transient test 411 has been added to the schedule to incorporate change of ANSI 3.5 in the 1993 revision.
All malfunctions are scheduled to be completed on a four year rotation with approximately 25% performed annually.
Attachment to AEP:NRC:113/lA Page 27 COOK NUCLEAR PLANT SIMULATOR ANSI 3.5 APPENDICIES A AND B ANNUAL TESTING SCHEDULE CRT"1 NPE-1 NPE-5 NPE-2 NPE-6 NPE-3 NPE-7 NPE-4 SS-01 ST-01 SS-02 ST-02 SS-03 ST-03 SS-04 ST-04 TMS-01 TMS-05 TRANS-09 TMS-02 TMS-06 TRANS-10 TMS"03 TMS-07 TRANS-ll TRANS-04 TMS-08 TEST DESCRIPTIONS:
CRT-1 COHPUTER REAL TIHE TEST NPE-1 NPE-2 NPE-3 NPE-4 NPE-5 NPE-6 NPE-7 RCS FILL AND VENT COLD SHUTDOWN TO HOT STANDBY REACTOR STARTUP PLANT STARTVP/POWER ESCALATION POWER REDVCTION PLANT COOLDOWN RCS DRAIN SS-1 STEADY STATE TEST 1 SS-2 STEADY STATE TEST 2 SS-3 STEADY STATE TEST, 3 SS-4 STEADY STATE TEST 4 ST-1 NATURAL CIRCULATION COOLDOWN W/VESSEL HEAD VOID FORHATION ST-2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
ST-3 STEAM GENERATOR TUBE RUPTVRE ST-4 UNIT 2 REACTOR TRIP, NOVEHBER 13, 1985 TMS-01 TMS-02 TMS-03 TMS-04 TMS-05 TMS-06 TMS-07 TMS-08 TMS-09 TRANS-10 TMS-ll HANVAL REACTOR TRIP TRIP OF ALL HAIN FEEDPUHPS CLOSURE OF ALL HSIV'S TRIP OF ALL REACTOR COOLANT PUHPS TRIP OP REACTOR COOLANT PIMP f23 HAIN TURBINE TRIP W/0 REACTOR TRIP HAXIHVH POWER RAHP 1002-752-1002 HAXIHVHSIZE LOCA WITH BLACKOUT HAXIHVH SIZE HAIN STEAHLINE RUPTURE SLOW RCS DEPRESSURIZATION TO SATURATION LOAD REJECTION
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Attachment to AEP:NRC:1134A Page 28 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE YEAR 1894 1994 1894 1894 1894 1994 1994 1994 1994 1894 1994 1994 1984 1984 1984 1994 1994 1994 1994 1994 1994 1994 1894 1994 1S94 1994 1994 1994 1994 1984 19S4 1894 1994 1994 1994 1S94 1994 1994 1994 1994 1995 1995 1895 1995 1995 1SS5 1995 1995 1995 1995 1SS5 1S95 1995 1S95 CC06 CS03 CV09 CV26 CM02 ED03 ED07 ED16 ED19 ED20 ED24 EG03 EG11 FP05 FWOS FW30 FW42 FW56 MS03 MS12 NI06 NZ10 RC03 RC07 RC17 RD08 RD12 RD16 RH15 RP03 RP12 RP20 RX08 RX16 RX24 RX28 SWO1 SW05 TC02 TU03 CC03 CC07 CH02 CS04 CV05 CV10 CV14 CV20 CV27 CV32 CW03 ED04 ED05 ED14 SEAL WATER HX TUBE LEAK REFUELING WATER STORAGE TANK LEAK LETDOWN TEHPERATURE CONTROL FAILURE REACTOR COOLANT PUMP fl SEAL PAILURE CW PUMP DISCHARGE VALVE FAILURE LOSS OF RESERVE AUXILIARYTRANSFORHER LOSS OF 480 VAC BUS AUXILIARIESAUTO BUS TRANSFER FAILURE ELECTRICAL GRID LOAD REJECTION ANN PANEL POWER SUPPLY FAILURE LOSS OF 250 VDC TRAIN "N" BATTERY HG AUTO VOLTAGE REG PAILVRE TO MANUAI DIESEL GENERATOR FAILURE TO TRIP CONTROL ROQH CABLE VAULT PIRE HAIN FEEDPUMP TURBINE TRIP LP HTR f3 LVL CONTROL VALVE PAILURE CONDENSATE STORAGE TANK LEAK PEED PUMP STEAM SUPPLY CONT PAIIURE HAIN STH LINE BREAK OUTSIDE CONT HSR DRAIN TK ALT DRAIN LVL CONT FAIL INTERMEDIATE RANGE HONZTOR FAILURE POWER RANGE CHANNEL FAILURE RCS LEAK REACTOR COOLANT PUMP LOCKED ROTOR PRESSllRIZER PORV FAILURE IN-HOLD-OUT SWITCH FAILURE FAILURE OF CONTROL RODS TO HOVE IRPI FAILURE SZ ACCUMULATOR N2 PRESSURE LOSS FAILVRE OF REACTOR TRIP BREAKER SPURIOUS ACTUATION OP SI TRAIN "B" K600 RELAY FAILURES PZR SPRAY VALVE AUTO CONTROL PAILVRE STEAH DUMP "PRES CONT" ERRATZC OPS FW CONTROL VALVE CONTROLLER PAILURE LOSS OF 480V HCC NON ESSENTIAL SERVICE MATER PUMP TRIP ESW PIPING RUPTVRE MAIN TURBINE FAILURE TO TRIP MAIN TVRBINE HIGH VIBRATION COMPONENT COOLING WATER RUPTURE COHPONENT COOLING HX TUBE RUPTVRE CONTAIN. PRESSURE TRANSHITTER FAILURE RWST LEVEL TRANSHITTER FAILURE LETDOWN HEAT EXCHANGER TUBE LEAK NORMAL CHG LINE LEAK INSIDE CONTAIN CHARGING PUMP SUCTION LINE LEAKAGE INADVERTENT BORATION REACTOR COOLANT PUHP t2 SEAL FAILURE PM PLOW TRANSHITTER (QFC"422) FAILVRE TRAVELING MATER SCREEN FOVLING LOSS OF EP SUPPLY TRANS TR-12-EP LOSS OP 4160 VAC BUS LOSS OF 250 VDC BATTERY CHARGER
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Attachment to AEP: NRC: 1134A Page 29 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST SCHEDULE 1995 1985 1985 1995 1995 1985 1995 1985 1995 1895 1895 1995 1895 1995 1995 1995 1995 1985 1995 1995 1995 1995 1995 1995 1985 1995 1985 1995 1895 1995 1995 1995 1995 1995 1995 1995 1985 1995 1895 1995 1895 1995 1995 1995 1995 1995 1995 1995 1995 1895 1995 1995 1895 1995 ED18 ED21 EG04 EGOS EG12 FP01 FW01 FW06 FW15 FW19 FW23 FW27 FW31 FW35 FW38 FW43 FW47 FW51 ZA01 IA05 MS04 MS09 MS13 MS18 NZ03 NZ07 NI11 NI15 RC04 RC09 RC14 RC19 RC25 RC29 RD01 RDOS RD09 RD13 RD17 RH03 RH07 RH12 RM01 RP05 RP09 RP13 RP15 RP17 RX01 RX05 RX09 RX13 RX17 RX21 GRID VOLTAGE OSCILLATION 4KV/600V AUX TRANSFORMER LOSS MG AUTO VOLTAGE REGULATOR FAILURE DG SPEED GOVERNOR PAILURE DG OUTPUT PREAKER FAILURE TO AUTO CLS FIRE PROTECTION SYSTEM RUPTURE MAIN FEEDWATER RUPTURE AT SG INLET MFP TURBINE SHEARED SHAFT (UNRZCOV)
FEEDWATER CONTROL VALVE FAILURE HP HEATER 46 TUBE RUPTURE HP HEATER t5 TUBE RUPTURE LP HTR f4 LVL CONTROL VALVE FAILURE LP HEATER f3 TUBE RUPTURE COND BOOSTER PP DISC PIPING RUPTURE CONDENSER TUBE LEAK HEATER DRAIN PUMP TRIP AUX FEEDPUMP SUCTION LINE LEAKAGE TDAFP TRIP a THROTTLE VALVE PAILURE PLANT AIR CCMPRESSOR TRIP CONT AIR SYS RUPTURE ZN CONTAINMENT MS LINE BREAK DOWNSTREAM SG STOP VLVS MSR TUBE RUFIURE MSR DRAIN TK ALT LVL CONT VALVE PhIL STEAM DUMP CONTROL VALVE FAILURE INCORRECT SR CHANNEL RESPONSE IR IMPROPER COMPENSATION PR CHANNEL OUTPUT OSCILLATION POWER RANGE CHANNEL BLOWN FUSE PRESSURIZER SURGE LINE LEAK REACTOR COOLANT PUMP SHAFT BREAK PZR HIGH GAS CONCENTRATION ZN VPR SP PRESSURIZER SAFETY VALVE FAILURE SG BD LINE LK DOWNSTREAM CONT ISOL S/G BLOWDOWN LEAK UPSTREAM OF CIV DROPPED CONTROL ROD EJECT OF RD WITH RUPT MECH HOUSING UNCONT ROD MOTION DEMAND (AUTOMATIC)
ROD GROUP FAILURE TO MOVE ROD GROUP STEP COUNTER PAILURE RHR HX BYPASS FLOW CONTROL VALVE PAIL RHR NORMAL CD SUC LINE LK INSIDE CONT SI LOOP CHECK VALVE LEAKAGE AREA RADIATION MONITOR PAILURE REACTOR COOLANT FLOW TRANS FAILURE FAILURE OF FW ISOLATION TRIP TO OCCUR FAILURE OF CI PHASE A TO AUTO ACTUATE SPURIOUS ACTUATION OF CI PHASE h FAILURE OF CI PHASE B TO MANUAL ACT RCS HOT LEG PRESSURE TRANS FAILURE PZR LVL TRANS FAILURE (PROT CHANNEL)
PZR PRES MASTER CONTROLLER FAILURE STEAM DUMP "TAVG" CONTROLLER FAILURE SG PRESSURE TRANSMITTER FAILURE SG FEED FLOW TRANSMITTER FAILURE
~s Attachment to AEP: NRC: 1134A I'age 30 COOK NUCLEAR PLANT SIMULATOR MALFUNCTXON TEST SCHEDULE 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1996 1996 1996 1996 1996 1996 1996 1996 1996 1996 1996 1996 1996 1996 1896 1996 1996 1986 1996 1986 1886 1996 1986 1996 1996 1986 1996 1986 1996 1996 1996 1996 1996 1996 1986 1996 1996 1896 1996 1896 1996 1996 1996 1996 RX25 SI01 SW02 SW06 TC03 TC07 TC12 TP03 TU01 TU05 CC04 CC06 CS01 CV01 CV06 CV11 CV15 CV21 CV26 CV33 ED01 ED06 ED10 ED17 ED22 ED26 EG05 EG09 EG13 FP02 FW02 FW07 FW16 FW20 FW24 FW26 FW32 FW36 FW40 FW44 FW46 FW52 IA02 IA04 MS01 MS05 MS10 MS14 MS21 NI04 NZ06 NZ12 RC01 RC05 FEEDWATER CONTROL VALVE OSCILLATION SAFETY INJECTION PUMP TRZP NESW PIPING RUPTURE IN TURB BLDG PP TURB OIL COOLING CONTROLLER FAILURE MAIN TURBINE AUTO TRIP FAILURE MAIN TURBINE INTERCEPT VALVE FAILURE MAIN TURBINE SPEED SIGNAL FAILURE MG STATOR COOLING SYSTEM RUPTURE AUXILIARYLUBE OIL PUMP TRIP MAIN TURBINE BEARING FAILURE MISC CCW HDR RUPTURE INSIDE CONTAIN.
CCW LEAKAGE INTO RCP BRNG OIL RES.
CONTAINMENT SPRAY PUMP TRIP LETDOWN LINE RUPTURE INSIDE CONTAIN.
QRV-301 FAILURE NORMAL CHG LINE LEAK OUTSIDE CONTAIN VCT LEVEL CONTROL VALVE FAILURE INADVERTENT DILUTION REACTOR COOLANT PUMP f3 SEAL FAILURE Bh FLOW CONTROLLER (QFC-421)
FAILURE LOSS OF 345KV BUS NO.
1 LOSS OF 600V MCC LOSS OF 120 VAC CONTROL ROOM POWER LOSS OP PLANT LIGHTING LOSS OF SWITCHGEAR CONT POWER TRAIN B LOSS OF 765KV DUMONT LINE MG OUTPUT BREAKER FAILURE TO TRIP DG VOLTAGE CONTROL FAILURE DG OUTPUT BREAKER FAILURE TO CLOSE INADV ACT OF CHARCOAL FILT FIRE PROT.
MFW RUPTURE BEFORE SG CHECK VALVE MAIN FEEDPUMP TURBINE BEARING FAILURE HP HTR g6 LVL CONT TRANSMITTER FAIL HP HTR f5 LVL CONT TRANSMITTER FAIL
- HP HEATER fS STEAM INLET RUPTURE LP HEATER f4 TUBE RUPTURE LP HEATER f3 STEAM INLET RUPTURE COND BOOSTER PP RECIRC VALVE PAILURE HOTWELL LEVEL CONTROLLER FAILURE HEATER DRAIN PUMP BEARING PAILURE AUX FEEDPUMP AUTO START FAILURE STEAM BOUND AFW PUMP PLANT AIR SYSTEM RUPTURE CONT AIR SYS RUPT IN TURBINE BUILDING MS LINE BREAK AT SG EXIT MAIN STEAM POWER RELIEF VALVE LEAK MSR COIL DRAIN TANK LVL CONT FAILURE MSR STEAM SUPPLY VALVE FAILURE AUX STM 150 0 HDR CONT VALVE PAILURE SR ENERGIZATION AT POWER (P10 PAILURE)
PR HL4NNEL UPPER DETECTOR FAILURE AUDIO COUNT RATE CHANNEL FAILURE RCS COLD LEG LOOP RUPTURE REACTOR VESSEL HEAD FLANGE LEAK
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4 Attachment to AEP: NRC: 1134A Page 31 COOK NUCLEAR PLANT SIMULATOR MAL1?UNCTION TEST SCHEDULE YEAR 1996 1996 1996 1996 1996 1996 1996 1996 1996 1896 1896 1996 1996 1996 1996 1896 1986 1996 1986 1896 1896 1996 1986 1996 1996 1996 1996 1896 1996 1886 1996 1886 1997 1997 1997 1997 1997 1997 1997 1997 1997 1987 1997 1897 1997 1997 1997 1897 1997 1997 1997 1897 1997 1897 RC09 RC15 RC21 RC26 RD02 RD06 RD10 RD14 RD16 RH04 RH06 RH13 RM02 RP06 RP10 RP16 RX02 RX06 RX10 RX16 RX22 RX26 SZ02 SW03 SW07 TC04 TC09 TC13 TP05 TU06 CC01 CC05 CC09 CC10 CS02 CV02 CV06 CV12 CV16 CV25 CV30 CW01 ED12 ED13 ED23 ED25 EG01 EG06 EG10 EG14 FP03 FW03 REACTOR COOLANT PUMP TRIP PRESSURIZER SPRAY VALVE FAILURE PRT RUPTURE DISC PAILURE FAILED FUEL ELEMENT BROKEN CONTROL ROD UNCONT ROD BANK CONTINUOUS WITHDRAWAL CR MOVE OPPOSITE TO DEMAND SIGNAL IMPROPER BANK OVERLAP ROD CONTROL MG SET TRIP RHR HX FLOW CONTROL VALVE FAILURE RWST SUPPLY LINE TO RHR PUMP RUPTURE SI ACC TANK CHECK VAIVE LEAKAGE PROCESS RADIATION MONITOR PAILURE SPURIOUS STEAM LINE ISOLATION FAILURE OF SI TO ACTUATE-AUTOMATIC FAILURE OP CZ PHASE h TO MANUAL ACT SPURIOUS ACTUATION OF CI PHASE B RCS HOT LEG TEMP TRANS FAILURE (NR)
PZR CAL LEVEL TRANSMITTER FAILURE PZR WATER LEVEL CONT OSCILLATION STEAM DUMP "PRES" CONTROLLER FAILURE MS TURB BYPASS HDR PRESS TRANS PAILURE SG PROGRQXKD LEVEL SIGNAL FAILURE FP TURBINE SPEED CONTROLLER FAILURE SAFETY INJECTION PUMP SHEARED SHAFT NESW RUPT ON LWR CONT VENT CLR SUP MT OIL TEMPERATURE CONTROLLER FAILURE MAIN TURBINE STOP VALVE PAILURE MAIN GENERATOR LOAD LIMITER PAIIURE TURBINE RUNBACK FAILURE STATOR COOLING WTR SYS HIGH COND TURBINE BLADE EJECTION COMPONENT COOLING WATER PUMP TRIP MISC CCW HDR RUPTURE IN AUX BUILDING CCW LEAK ON RHR PUMP SUPPLY LINE CCW LEAKAGE INTO RCP L.BRNG OIL RESERV.
CONTAIN. SPRAY PUMP. SUCTION BLOCKAGE LETDOWN LINE RUPTURE OUTSIDE CONTAIN.
LETDOWN LINE RELIEF VLV SV-51 LEAKAGE CCP FLOW CONTROL VALVE FAILURE VCT LEVEL TRANSMITTER FAILURE RCP THERMAL BARRIER BX RUPTURE REDUCED CCP CAPACITY CIRCULATING WATER PUMP TRIP LOSS OF 250 VDC POWER (TRAIN h)
LOSS OF 250 VDC POWER (TRAIN B)
LOSS OF SWITCHGEAR CONT POWER TRAIN h LOSS OF 765/345KV TRANSFORMER BANK I4 MAIN GENERATOR TRIP DIESEL GENERATOR TRIP DIESEL GENERATOR FAILURE TO START DG RUNNING RELAY FAILURE DIESEL GENERATOR ROOM C02 ACTUATZON MFW RUPT BETWEEN FEEDFLOW ELMT & FRV
Attachment to AEP: NRC: 1134A Page 32 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE 1997 1997 1997 1997 1897 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1987 1997 1997 1997 1997 1997 1997 1997 1997 1997 1897 1897 1997 1997 1997 1987 1997 1987 1997 1997 1897 1897 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 1997 FW12 FW17 FW21 FW25 FW29 FW33 FW37 FW41 FW4 5 IA03 MS02 MS06 MS11 MS16 NI01 NI05 NI09 NI13 RC02 RC06 RC10 RC11 RC12 RC16 RC23 RC27 RD03 RD07 RD11 RD15 RD19 RH01 RH05 RH09 RH14 RM03 RP01 RP07 RP11 RP19 RP21 RX03 RX07 RXl1 RX19 RX23 RX29 SI03 SWOT TC01 TC05 TC10 TP01 WD01 FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK HP HTR t6 LVL CONTROLLER AUTO FAILURE HP HTR f5 LVL CONTROLLER AUTO FAILURE HOTWELI PUMP TRIP LP HTR f3 LVL CONT TRANSMITTER FAIL LP HEATER BYPASS VALVE FAIIURE HOTWELL PUMP DISCHARGE PIPING RUPTURE HW LEVEL CONTROL TRANSMITTER FAILURE HEATER DRAIN PUMP ELO VLV FAILS OPEN CONTROL AIR COMPRESSOR TRIP MAIN STEAM LINE BREAK AT SG EXIT STEAM GENERATOR SAFETY VALVE LEAK MSR COIL DRAIN TANK LVL CONT VLV FAIL STEAM SEAL CONTROLLER FAILURE SOURCE RANGE MONITOR FAILURE SOURCE RANGE CHANNEL SPIKES PR CHANNEL LOWER DETECTOR FAILURE SOURCE RANGE INSTRUMENT BLOWN FUSE RCS HOT LEG LOOP LEAK RCS EMERGENCY VENT LEAKAGE RCS COLD LEG LEAK REACTOR COOLANT PUMP HIGH VIBRATION RCP LOWER BEARING OIL RESERVOIR LEAK PRESSURIZER STEAM SPACE MANWAY LEAK STEAM GENERATOR TUBE RUPTURE RTD BYPASS MANIFOLD FLOW DEGRADATZON STUCK CONTROL ROD (TRIPPABLE)
UNCONT ROD BANK CONTINUOUS INSERTION AUTO CONTROL ROD SPEED FAILURE IRPI POWER LOSS IMPROPER ROD WORTH RHR PUMP TRIP RHR HEAT EXCHANGER TUBE LEAK RHR PUMP SUCTION PIPE RUPTURE SZ ACCljMULATOR TANK LEVEL LOSS EBERLINE AREA RADIATION MONITOR FAILURES REACTOR TRIP ACB AUTO TRIP FAILURE FAILURE OP STEAM LINE ISO TO ACTIVATE FAILURE OP SZ TO ACTUATE-MANUALLY TRAIN "h" K600 RELAY FAILURES FAILURE OF FWZ TRIP TO OCCUR RCS COLD LEG TEMP TRANS FAILURE (NR)
REDUCED PRESSURIZER HEATER CAPACITY SG RELIEF VALVE CONTROLLER FAILURE TURBINE IMPULSE TRANSMITTER FAILURE SG LEVEL TRANSMITTER FAILURE FPC-250 TRANSMITTER FAILURE HIGH HEAD SZ LINE RUPTURE ESSENTIAL SERVICE WATER PUMP TRIP MAIN TURBINE TRIP MAIN TURBINE CONTROL VALVE FAILURE MAIN GEN OPERATING DEVICE FAILURE TURBINE AUX COOLING PUMP TRIP RELEASE OF RADIOACTIVE GAS FRCM GDT
Attachment to AEP: NRC: 113%A Page 33 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE YEAR 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 CC02 CC06 CHol CS03 CVO4 CV09 CV13 CV17 CV26 CV31 CW02 ED02 ED03 ED06 ED07 ED11 ED15 ED16 ED19 ED20 ED24 EG03 EG07 EG11 EG15 FP05 FW05 FW18 FW22 FW26 FW30 FW34 FW38 FW42 FW46 FW50 FW54 FW56 MS03 MS08 MS12 MS17 NI02 NI06 NI10 NI14 RC03 RC07 RC13 RC17 RC24 RC28 RD04 RD08 CCW PUMP FAILURE TO AUTO START SEAL WATER HX TUBE LEAK CONTAIN. PRESS.
RELIEF VLV FAILURE REFUELING WATER STORAGE TANK LEAK LETDOWN LINE ORIFICE ISO. VLV FAILURE LETDOWN TEMPERATURE CONTROL FAILURE CHARGING PUMP TRIP VOLUME CONTROL TANK LEAKAGE REACTOR COOLhllT PUMP tl SEAL FAILURE BACKPRESSURE CONT VLV FAILURERV-200 CW PUMP DISCHARGE VALVE FAILURE LOSS OF AUXILIARYTRANSFORMER LOSS OF RESERVE AUXILIARYTRANSFORMER LOSS OF 600 VAC BUS LOSS OF 480 VAC BUS LOSS OF 250 VDC BUS LOSS OF VITAL INST BUS STATIC SWITCH AUXILIARIESAUTO BUS TRANSFER FAILURE ELECTRICAL GRID LOAD REJECTION ANN PANEL POWER SUPPLY PAILURE LOSS OF 250 VDC TRAIN "N" BATTERY MG AUTO VOLTAGE REG FAILURE TO MANUAL DG SPEED CONTROL FAILURE DIESEL GENERATOR FAILURE TO TRIP MG SEAL OIL UNIT PIPING RUPTURE CONTROL R(XX4 CABLE VAULT PIRE MAIN FEEDPUMP TURBINE TRIP HP HTR 46 LVL CONTROL VALVE FAILURE HP HTR 45 LVL CONTROL VALVE FAILURE LP HTR 44 LVL CONT TRANSMITTER PhIL LP HTR 43 LVL CONTROL VALVE FAILURE CONDENSATE BOOSTER PUMP TRIP LOSS OF CONDENSER VACUUM CONDENSATE STORAGE TANK LEAK AUX FEEDPUMP TRIP TDAFW PUMP SPEED CONTROLLER FAILURE FDWTR RUPT OUTSIDE CONTAINMENT FEED PUMP STEAM SUPPLY CONT PAILURE MAIN STM LINE BREAK OUTSIDE CONT SG STOP VALVE DRIFTS SHUT MSR DRAIN TK ALT DRAIN LVL CONT FAIL STEAM SEAL CONTROLLER OSCILLATION SOURCE RANGE HV FAILURE TO DEENERGIZE INTERMEDIATE RANGE MONITOR PAILURE POWER RANGE CHANNEL FAILURE INTERMEDIATE RANGE CllhNNEL BLOWN FllSE RCS LEAK REACTOR COOLANT PUMP LOCKED ROTOR RCP UPPER BEARING OIL RESERVOIR LEAK FRESSURIZER PORV FAILURE STEAM GENERATOR TUBE LEAK PRESSURIZER INSTRUMENT LINE LEAKAGE STUCK CONTROL ROD (UNTRIPPABLE)
IN-HOLD-OUT SWITCH FAILURE
ie Attachment to AEP:NRC:1134A Page 34 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 1998 RD12 RD16 RH02 RH06 RH11 RH15 RP03 RP08 RP12 RP16 RP20 RX04 RX08 RX12 RX16 RX20 RX24 RX27 RX28 SW01 SW05 TC02 TC06 TC11 TP02 TU03 FAILURE OF CONTROL RODS TO MOVE IRPZ FAILURE RHR PUMP SEAL FAILURE RHR INJ HDR RELIEF VALVE PhIL (SV-104)
RHR RET FLOW TRANS FAILURE (ZPI-335)
SI ACCUMULATOR N2 PRESSURE LOSS FAILURE OP REACTOR TRIP BREAKER SPURIOUS FEEDWATER ISOLATION TRIP SPURIOUS ACTUATION OF SZ FAILURE OP CI PHASE B TO AUTO ACTUATE TRAIN "B" K600 RELAY FAILURES PRESSURZZER PRESSURE TRANS FAILURE PZR SPRAY VALVE AUTO CONTROL FAILURE MS RELIEF VLV CONTROLLER OSCIL1ATION STEAM DUMP "PRES CONT" ERRATIC OPS SG STEAM FLOW TRANSMITTER PAILURE FW CONTROL VALVE CONTROLLER PAILURE PEED PUMP DP CONTROLLER PAILURE LOSS OP 480V lid NON ESSENTIAL SERVICE WATER PUMP TRIP ESW PIPING RUPTURE MAIN TURBINE FAILURE TO TRIP MAIN TURBINE ERRATIC CONTROL VALVE AUTO LOAD SET OSCILLATION TURBINE AUX COOLING PIPING RUPTURE MAIN TURBINE HIGH VIBRATION
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